ML20141G456
| ML20141G456 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 04/18/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20141G401 | List: |
| References | |
| NUDOCS 8604230399 | |
| Download: ML20141G456 (8) | |
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I unc rona su u.s. NUCLEAREEULATORY CcMMISSCN I - CERTIFICATE CF CCC'PLIANCE I I io cFR,n FOR RADIOACTIVE MATERIALS PACKAGES lI D Revision NuuSER C PACKAGE lOENTIFICATsON NUM8ER o PAGE NUMBER e TOTat a suM8th PAGES t.a CERTtFICATE NUMBER g! 5942 11 USA /5942/B( )F 1 4 ll I! : eRE4ustE a Ths certificate is issued to certify that tne packaging and contents descrieed in item 5 beiow. meets tne sophcabie satoty standards set fortn in Title 10. Code ll 1
l' l of Federal Regulations. Part 71. ' Packaging and Transportation of Radioactive Material? [I I e Tnis certiticate does noi rei.e.e tne consignor from comphance wiin any requirement of tne reguiationi ce ine u s o.oartm.ni ce 7,ansportation or otn.r ;l ;
I appucacie regulatory agencies. including tne government of any country tnrougn or into wn.cn the package wiu be transported i l
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, T E eAsis of A SAFETY ANALYSIS,RE T,0 ,T;E ,C A,G,E ,PPL C I General Electric Company General Electric Application dated May 30, 1985, :I Ij Vallecitos Nuclear Center as suoplemented. il I Pleasanton, CA 94566 ,1 I I I
E 71-5942 I c. Doc =ET NuusER ll a CONotTIONS I This certificate is conditional upon fulfilhng the requerements of 10 CFR Part 71, as apphcable and the conditions specified below Ii ll i
I, 5 lI f (a) Packaging j f (1) Podel No.: 700
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l (2) Description
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I I g A steel encased lead shielded shipping cask enclosed by a double- g I walled protective .iacket of the sane shape with a rectangular baseplate. 1 I The cask is a double-walled steel circular cylinder, 37-inch-diameter I I by 65-inch high with a central cavity 15-inch-diameter by 40-inch lI
% high. Approxinately 10.25 inches of lead surround the central cavity. ll The cask 'is eouipped with a cavity drain line, pressure relief valve lI
[l set at 100 psig, and lifting device. Closure is accomplished by a silicone rubber gasketed and bolted steel lead filled plug. The
!I ll l lh li naxinun gross weight of the package (contents, cask assembly, protective il Il .iacket and base) is 35,500 pounds. lI I l I; The cask may be modified with a 14-inch high cavity extension with an ;l
- l I! additional silicone rubber gasket. The modified cask is 79 inches ij Il high. The naxinun gross weight of the oackage (contents, nodified i, cask assembly, protective jacket and base) is 40,200 pounds.
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Il g (3) Drawings llI I il I The packaging is constructed in accordance with the following General 'I l- Electric Company Drawing Nos.: 12904768, Rev. 3; 12904769, Rev. 4; I and 12904770, Rev. 5. l l I 1
g Lifting and/or tie-down devices which are a structural part of the I l package must be in accordance with the above drawings. .I P
'l I !I I il I !I l ll l h42039986041s C Docg 07105742 N I
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- 1. Page 2 - Certificate No. 5942 - Revision No. 11 - Docket No. 71-5942 I
- D Ii l S. (b) Contents j
! (1) Type and fom of material )
I 'I I (i) ~ Byproduct, source, and special nuclear material as solid oxide or .I 3> aetal in the form of fuel rods, or plates, fuel assemblies, or l
meeting the requirements of special fom radioactive material . ;j#
i I i (ii) Co-60 metal contained within sealed liner and sleeve described in i 1, Neutron Products, Inc. Drawing Nos. 240139, Sheets 1 through 3, I I Revision No. F and 240138, Revision No. .
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(2) Maxinum quantity of material. per package j si I i Not to exceed 700 pounds (including shoring), and g 1 I I (1) 740 gm U-235, provided that the maximun U-235 enrichment does not 1 '
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} exceed 6 weight percent; or f1 (ii) 1,200 gm U-235, provided that the fuel material is in the form of MTR-type fuel elenents with a ninimun active fuel length of 23 'u 1 inches; or 'l '
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} (iii) 220 gm fissile material; or I
'l 13' (iv). .I,650 gn U-235, provided thai the maximun U-235 enrichment does !g 1 not exceed 3.5 weight. percent and' the fuel naterial is in the 'I 1 fom of 88 rods loaded;with 0.376-inch-diameter pellets with a j minimun active fuel length of 37 inches; or jll j j (v) those values present'ed'in Figure 1 U0, Weight Limits forff'odel 700 j Shipping Container .of Exhibit A to this application, applicable l p
1 to fuel naterial in the form of rods with a mininun pellet diameter :I 1 of 0.40. inch; or lI
.1 'I I (vi) 5,100 gn U-235, provided the fuel is in the fom of ETR-type fuel ]!y elenents (GETR. Fuel) with each element containing no more than
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- j 510 gm U-235 and inserted in the spaced stainless steel fuel !g
-1 shipping basket described in GE Drawing No. 10604150, Rev. 0.; or l
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) (vii) 6,200 gm U-235, provided the fuel is in the fom of MURR TRTR j type elements containing not more than 775 gn U-235 per element; loaded and spaced in the stainless steel fuel shipping basket as
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!g j:j! described in MURR Drawing No.1228, Sheets I thru 5, Revision 0. !g
.); Fuel elements shall have at least 150 days cooling time since (1
-1 last reactor operation; or ;I
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) (viii) 3,510 gn U-235 provided the fuel is in the fom of MTR-type fuel elements with each element containing no more than 351 gm U-235 j!g
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ig and inserted in a spaced stainless steel fuel shipping basket ll lI described in GE Drawing No. 10604150, Rev.1 for GETR fuel . A tu shoring device to limit vertical notion of the fuel elements must ;I lI!
J be included. j t >l I! i i
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%-m-mm _m mM26 i li .
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}' CONDITIONS (continued) -
l P' age 3 - Certificate No. 5942 - Revision No.11 - Docket No. 71-5942 g 4
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1 K 1 5. (b) (2) (continued) Il ;
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l (ix) 7,020 gn U-235 provided the fuel is in the form of fiTR-type fuel lg j elenents with each element containing no nore than 351 gm U-235 y 1 3 inserted in a spaced stainless steel fuel shipping basket described 'R 1 in GE Drawing No.106D4150, Rev.1, for 24-inch length fuel . k -
i Each shipment rust contain 20 fuel elements in 2 fuel baskets k -
l with the spacer plate shown on CE Drawing No. 21886061, Rev. O, j located between the baskets. {
i > 9 3 (3) tiaxinun quantity of radioactive decay heat per package i g 1 i =
} (1) 6,500 watts for dry shiprents, or j
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.g, (ii) 1,500 watts 'for wet shipments, provided that the cavity shall contain at least a 1,000 cu in air void (at standard temperature g:
3 and pressure) at the time of delivery to a carrier for transport. E. j i I: =
i (c) Fissile Class III l- -
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. Maxinun nunber of packages per shipment 2 h
1 s ,L; 4 1 6. The liner required for Co-60 metal which does not meet the requirement for t'
' 1, special fom radioactive material, must be dried, leak tested,cand back-filled I:
- I with an inert gas in accordance with Enclosure 2, Rev. 2 to Neutron Products, 1 2 3
Inc. letter dated February 28, 1986.
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3 Shoring cust be provided to minimize: movement of contents during accident conditions t
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1 of transport. L i -
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4 8. Prior to each shipment (except for contena. neeting the requirements of special 0 2 g
l fom radioactive material), the pack of detemining that a leakage of 10"3ge atmmust cr#/sbe leak tested at standard by a method temperature and capable b h- 8 i pressure is not exceeded. ,tj i 1 ;t. -
4; 9. Prior to each shipment the silicone rubber lid gasket (s) nust be inspected. } $
4 This gasket (s) nust be replaced if inspection shows any defects or every twelve d ly (12) months, whichever occurs first. Cavity drain line nust be sealed with j -
appropriate sealant applied to threads of pipe plug. 4 i 1 't 1 10. The applicant must confirm annually that the pressure relief valve is operable ) i 4; at 100 psig. $ 1 i a -
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- 11. When needed, sufficient antifreeze in the cask cust be used to prevent damage of any component of the package due to freezing.
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1 lt L 12. Fabrication of additional packagings is not authorized. l[
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- 13. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12. j a
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t 14. Expiration date: July 31, 1990. lf ; -
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l 1l conom:Ns (continusm 'g 1 .I 1;, Page 4 - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942 ,a 1 :p 1 l l I REFERENCES !
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General Electric application dated Fay 30, 1085. :I ,
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Supolements dated: June 5 and 7, August 7, and September 16, 1985. fil 1 University of Missouri letter dated March 20, 1980. g 1 E 1 Appendix 6-A regarding University of tiissouri's quality assurance program is not E j considered part of this application.
(
'l 'F r g1 Neutron Products, Inc. supplements dated: November 11, 1985; and February 28, Parch 11 g
) and 31, and April 1 and 10,1986'. g 1
I 1 FOR THE U.S. NUCLEAR REGULATORY COMrilSSION I
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1 l 1 I 1 - Charles E. MacDonald, Chief . N
-1 Transportation' . Certification Branch I l
Division of Fuel Cycle and. I l l, Material Safety, fitSS !
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Transportation Certification Branch Approval Record Model No. 700 Package Docket No. 71-5942 By application dated November 11, 1985, as supplemented, February 28, March 11 and 31, and April 1 and 10,1986, Neutron Products, Inc. requested to ship cobalt-60 netal in the Model No. 700 package (cask). The Model No. 700 cask lid seal may not prevent dispersal of non-special form ma terial . Therefore, the cobalt is contained within a vacuun-dried and helium-filled liner inside the Model No. 700 cask. The scope of this evaluation is limited to the perfornance of the liner / cask combination under both nornal transport and hypothetical accident conditions.
STRUCTURAL Normal Conditions of Transport (10 CFR 671.71)
Heat and Cold
- The liner components are fabricated mainly from Type 304 stainless steel,' it can withstand the heat and cold tenperature range defined in 10 CFR Part 71 and is not susceptible to brittle fracture at tenperatures encountered in transport.
Reduced External Pressure and Increased External Pressure
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The liner and its contents will not be effected by the range of external pressures defined in 10 CFR Part 71, since the Model No. 700 cask is capable of withstanding those external pressures without loss 'of structural integrity.
Vibration The Model No. 700 cask and the liner is shipped in an upright p osition. The only vibration that the liner is likely to see is a lateral rocking motion inside of the Model No. 700 cask cavity.
However, this motion is restrained by the aluminun sleeve which fills the space between the wall of the liner and wall of the cavi ty.
Waster Spray Since water spray has no adverse effect on the Model No. 700 cask, the liner will not be effected either.
Free Drop The liner can withstand the free drop' requirement in 10 CFR 671.71(c)(7) as demonstrated by neeting the more stringent requirements specified in~ 10 CFR 971.73(c)(1) for the hypothetical accident conditions.
Corner Drop Not applicable for this design case.
Compression Not applicable, cask exceeds 10,000 pounds.
Penetration Since there is no damage to the Model No. 700 cask from the penetration impact prescribed by 10 CFR Part 71, the line will not be damaged either. -
Hypothetical Accident Conditions (10 CFR $71.73)
Free Drop The applicant's evaluation of the liner / cask following the 30-foot drop test of 10 CFR Part 71 is based on the results of analyses using analytical techniques. Four drop orientations for the package have been evaluated. They are: top end drop, botton end drop, side drop, and oblique angle drop. For each of the drop orientations, the analyses indicated that the liner, including the bolted closure and pressure boundary fittings on the top plate, would retain its contain1ent integrity.
Shielding of radioactive material is provided by the Model No. 700 cask. The Model No. 700 cask was previously demonstrated to meet the requirenents of 10 CFR Part 71, it .is concluded that shielding effectiveness for the liner / cask combination would not be reduced resulting from 30-foot drop tests.
Puncture The applicant used analytical techniques and reasoned argument to evaluate the liner for the 40-inch puncture test. The results indicate that the 6-inch diameter pin would not penetrate through the liner. Therefore, the liner integrity would not be effected.
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Thermal Under the~ fire test prescribed in 10 CFR Part 71, the maximun temperature inside the Podel No. 700 cask ray reach 464*F. The stainless steel construction of the liner, the gasket, and pressure boundary fittings on the top plate will have no problen retaining their functions at this temperature. The maximum internal pressure produced at.this temperature @s30 psig) would be within the cask capability of the seal and the liner. Furthermore, althouah the stainless steel liner and the aluminum sleeve have different coefficients of thermal expansion, adeouate axial and radial clearances would still exist between the cask cavity, the outside of the sleeve, and the liner at the temperature stated above. Therefore, the liner / cask cambination would retain its integrity during exoosure of the Podel No. 700 cask in the hypothetical fire test of 10 CFR Part 71.
Immersion Fissile Material Not applicable, fissile packages only. .
Immersion - All Packages The liner has been designed for a differential pressure of 150 psi.
Therefore, the liner is capable of withstanding an external pressure of 21 psig.
CONTAINMENT The requested contents is to ship nickel plated, aluminun encased. -
irradiated Cobalt-60 sources in the Podel No. 700 cask. The cask is presently approved for various radioactive naterials in special form.
The condition of-the encapsulation of the Co-60 netal is not known, but their integrity cannot be assumed because some sources have leaked neasurable amounts of radioactive material. To provide containment, a sealed vacuun-dried and helium-filled liner is proposed. The liner is helium bubble tested to a pressure differential of 2-3 psig while still in the pool . The stainless steel-asbestos gasket has high temperature service rating Gv1000*F) and will not be significantly effected by normal nor accident thermal conditions. The proposed gas bubble test is considered adequate for containment demonstration for the requested Co-60 metal sources.
The liner is dried by naintaining a vacuum of 29.5-inch Hg (0.5-inch Hg absolute pressure) for 5 minutes with the vacuum pump turned off. This vacuum corresponds to a saturation tenperature of 58.5 *F which is lower than the expected pool tenperature. This procedure should assure that the water has been removed from the liner prior to shipment.
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OPERATING PROCEDURES
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Enclosure 2 Pevision No. 2, to the applicant's letter dated February 28, 1986, provides a sumnary of procedures for loading, drying, leak testing, and back filling the liner with an inert gas. The drying, and leak testing, and back filling procedures have been made a condition of the a pproval .
Charles E. acDonald, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, NHSS Date: OEII8I000 m
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